ML20148Q693
| ML20148Q693 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/09/1977 |
| From: | Curran J SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20148Q696 | List: |
| References | |
| S-V-2.13, TAC-07099, TAC-7099, NUDOCS 8802010173 | |
| Download: ML20148Q693 (4) | |
Text
,_
[
h-g I
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S-V-2.13 September 9, 1977 i*
INSERVICE INSPECTION CLASS 3 COMPONENTS I.
OBJECTIVE This procedure defines the inservice inspection requirements for ASME Code Class 3 components at San Onofre Unit 1 and assures compliance with Technical Specification 4.7.
Furthermore, this procedure intends to meet the requirements of ASME Code and Addenda in effect as of July 1,1977 (Reference 1) to the maximum extent practical.
II. CONDITIONS A.
The examination requirements of the procedure are to be performed in compliance with the requirements of RefGrence I to the maximum extent practical.
B.
The Class 3 inservice inspection program delineated herein covers a ten year inspection interval comencing on January 1, 1978 and terminating on December 31, 1987.
C.
The requirements of this procedure remain in effect for a maximum period of forty (40) months, comencing)on January 1, 1978. prior to the expiration of the forty (40 month period, the inservice inspection program shall be reviewed and revised as necessary, in accordance with the requirements of 10 CFR 50.55a(g).
D.
Class 3 components, for the purposes of inservice inspection, are itemized in Tables 3A and 3B of Reference 2.
III. REQUIREMENTS The Class 3 inspection requirements delineated in Reference 1 consist basically of two programs: a system pressure test once per inspection interval and an operational leakage test by the expiration of 1/3 of the inspection interval.
A.
System Pressure Test 1.
100% of the Class 3 components shall be subjected to a system pressure test by the expiration of the inspection interval (December 31,1987).
2.
The system test pressure shall confonn to the requirements specified in Article IWD-5000 of Reference 1.
3.
The test temperature shall be at a temperature that will minimize the possibility of brittle fracture.
- Nonnally, ambient temperature or above will suffice for Class 3 components.
8802010173 770928 PDR ADOCK 05000206 p
PDR J
a SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S-V-2.13 September 9, 1977 Page 2 4.
The pressure-retaining components shall be visually examined while the system is under the test pressure and temperature.
The test pressure and temperature shall be maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the performance of the examinations.
5.
In the case of storage tanks, the nominal hydrostatic pressure developed with the tank filled to its design capacity shall be acceptable as the system test pressure.
6.
Open-ended portions of a system (e.g., suction or drain line from a storage tank) extending to the first shutoff valve may be exemr.ced from these test requirements.
B.
Operational Leakage Tests 1.
100% of the Class 3 components shall be examined while in operation or during system inservice testing (system pressure test) by the expiration of every one-third of each inspection interval.
IV. EXAMINATION A.
Visual examination shall be conducted for evidence of component leakages (other then controlled or collected leakages), structural distress, or corro? ion when the system is undergoing either a system inservice test, component functional test (i.e., valves and pumps), operational leakage test, or a system pressure test.
B.
The examination, which may be conducted without the removal of insulation, shall be performed by inspecting (1) the exposed of leakage and (joints in component insulation to locate evidence surfaces of and 2) the floor areas (or equipment) directly under-neath components for evidence of accumulated leakage that may drip from components.
C.
Examination of insulation joints along vertical surfaces of vessels, walls, and piping need not be perfomed, provided the lowest terminal ends of vertical surfaces are examined, and the insulation design is such that any leakages originating along the vertical surfaces can accumulate the leak from the insulation joint at the lowest elevation.
r a
9 SAh ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S-V-2.13 Page 3 September 9, 1977 D.
At locations where leakages are normally expected and collected (e.g., valve stems, pump seals), the examination shall verify that the leakage collection system is operative.
E.
During the examination, particular attention shall be given to the insulated areas of components constructed of ferritic steels to detect evidence of boric acid residues whose source derives from borated reactor coolant, and which may have accumulated during the service period preceding the examination.
In the event boric acid residues are &,tected, the insulation shall be renoved from the components to the extent necessary to permit visual examination of the wetted surfaces in order to detect evidence of corrosion.
1.
An evaluation of the effect of any corroded area upon the structural integrity of the component shall be performed in accordance with the provisions of IWA-3000, 2.
Repairs of corroded areas or component replacement, if necessary, shall be performed in accordance with the procedures of IWA-4000.
F.
In the case of buried components (e.g., undergound piping), where valves are provided to permit isolation of the buried portions of piping, a systai pressure test shall be conducted in lieu of the visual examination. A loss of system pressure during the test shall constitute evidence cf component leakago.
G.
Supports (restraints) and hangers for components exceeding four-incti nominal pipe size whose structural integrity is relied upon to withstand design loads when the system function is required shall be visually examined to detect any loss of support capability, and evidence of inadequate restraint.
V.
CORRECTIVE HEASURES If leakages (other than normal controlled leakages) are detected during the performance of a system pressure test, or operational leakage test, the source of leakage shall be located and the area shall be examined to the extent necessary to establish the require-ments for corrective action.
Repairs, if necessary, shall be in accordance with the requirements of IWA-4000 of Reference 1 to the maximum extent practical.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S-V-2.13 September 9,1977 Page 4 VI.
IMPLEMENTATION The Class 3 items delineated in Tables 3A and 3B of Reference 2 generally include the following systems (or portions thereof):
l 1.
Component Cooling Water System:
a.
RCP bearing oil coolers and thennal barrier coil b.
RHR heat exchangers c.
Excess letdown heat exchanger (Shell side only) d.
Sample heat exchangers (Shell side only) l l
2.
Spent fuel pit and cooling water system.
3.
Auxiliary feedwater system.
4.
Diesel jacket water cooling system, 5.
Salt water cooling system tup to and inicuding the component j
coolinC Seatexchangers).
A.
Prior to 1988, all components delineated in Reference 2 as Class 3 components shall be subjected to a system pressure test in accordance with the requirements of this procedure and Reference 1.
B.
Prior to April 30, 1981 all components delineated in Reference 2 as Class 3 components shall be subjected to an operational leak test or a system pressure test in accordance with the requirements of this procedure and Reference 1.
VII. RECORDS The records of the visual examinations conducted during a system pressure test or operational leakage test shall consist of itemization of the number and location of leaks found in the system (s) and the actions taken.
VIII.
REFERENCES 1.
American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI,1974 edition, including l
Addenda through Sumer,1975.
2.
San Onofre Nuclear Generating Station, Unit 1. Classification I
l of ASME Class 1, 2, and 3 Systems and Components, including Addendum 1, 1
l
~b W
h J. M. Curran Plant Manager l
GTM:ye L
l